FireDOC Search

displaying 101 - 110 results in total 142

  • Powers, C. S.
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    Safety Analysis Report 231-Z Building.
    Battelle Pacific Northwest Lab., Richland, WA
    BNWL-CC-1924, March 1989, 81 p.

  • Rockett, J. A.
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    Experience in the Use of Zone Type Building Fire Models.
    Fire Modeling and Analysis, Washington, DC
    Fire Science and Technology, Vol. 13, No. 1/2, 61-70, 1993

  • Buzzard, R. J.; Sheffler, K. D.
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    Effect of Long-Time, Elevated-Temperature Exposures to Vacuum and Lithium on the Properties of a Tantalum alloy, T-111.
    NASA Lewis Research Center, Cleveland, OH
    National Aeronautics and Space Administration, Washington, DC, NASA TN D-7548, March 1974, 33 p.

  • U.S. Nuclear Regulatory Commission
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    NRC Safety Research in Support of Regulation, FY 1993.
    Nuclear Regulatory Commission, Washington, DC
    NUREG-1266, Vol. 8, June 1994, 89 p.

  • Benjamin, A. S.; Brown, N. N.
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    Development of Fast-Running Thermal and Structural Response Models for Probabilistic Analyses of Complex Systems.
    Sandia National Labs., Albuquerque, NM
    Department of Energy, Washington, DC,
    PSAM-II Proceedings. An International Conference Devoted to the Advancement of System-Based Methods for the Design and Operation of Technological Systems and Processes. Volume 2. Sessions 37-72. March 20-25, 1994, San Diego, CA, Apostolakis, G. E.; Wu, J. S., Editors, 037/1-4 p., 1994

  • Chiao, T.; Wood, S. A.; Shen, P. K.; Baker, R. B.; Gluekler, E. L.
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    Analyses of Postulated ALMR Containment and Steam Generator Building Accidents Using the CONTAIN-LMR Code.
    Westinghouse Hanford Co., Richland, WA
    Department of Energy, Washington, DC, WHC-SA-2121-FP, January 1994,
    ARS'94: International Topical Meeting on Advanced Reactor Safety. April 17-20, 1994, Pittsburgh, PA, 1-11 p., 1994

  • Kersting, E.; vonLinden, J.; Muller-Ecker, D.; Werner, W.
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    Safety Analysis for Boiling Water Reactors: A Summary.
    Gesellschaft fur Anlagen und Reaktorsicherheit (GRS) mbH, Koeln, Germany
    GRS-98, July 1993, 110 p.

  • Lowry, W.; Vigil, R.
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    Prioritization of Reactor Control Components Susceptible to Fire Damage as a Consequence of Aging.
    Science and Engineering Associates, Inc., Albuquerque, NM
    Sandia National Labs., Albuquerque, NM; Nuclear Regulatory Commission, Washington, DC, NUREG/CR-6103, January 1994, 45 p.

  • Restrepo, L. F.
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    Fire Accident Analysis Modeling in Support of Non-Reactor Nuclear Facilities at Sandia National Laboratories.
    Sandia National Labs., Albuquerque, NM
    Department of Energy, Washington, DC, SAND-93-0463C, 1993, 2 p.

  • Striebich, R.; Zelina, J.; Grinstead, R.; Blust, J.
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    Studies of Halon Decomposition in a Well Stirred Reactor.
    University of Dayton Research Inst., OH
    University of California, Berkeley. Toxic Toxic Combustion Byproducts. 4th International Congress. ABSTRACTS ONLY. June 5-7, 1995, Berkeley, CA, 70 p., 1995